Yttrium-90 and Rhenium-188 Radiopharmaceuticals for Radionuclide Therapy

TABLE 3.3. RESULTS FOR 90 Sr/ 90 Y ELECTROCHEMICAL GENERATOR
Electrolysis (separation) Volume (mL) Activity (MBq)
Amount of
Y-90 electroplated (%)
Solution I a (before process) 30 431.79 0
Solution I a (after 30 min) 30 330.78 23
Solution I a (after +30 min) 30 223.11 32
Electrolysis (reversal) Volume (mL) Activity (MBq) Y-90 recovery (%)
Solution II b (after 5 min) 29.77 83.25 82
Solution II b (after +5 min) 28.95 30.93 29
a
b
Solution I: 1 mol/L HNO 3 solution, pH5.0.
Solution II: 1 mol/L HNO 3 solution, pH4.0.
3.1.3. Strontium-90/yttrium-90 generators via colloid formation
The basis was to form colloids of yttrium in hydroxide medium and then
dissolve colloidal particles with HCl. The initial experiments involved the use
of different filter materials and a solution of 85 SrCl 2 dissolved in H 2 O with
1 mol/L HCl. The separation efficiency was evaluated using γ spectrometry, and
the results are shown in Fig. 3.9.
According to Fig. 3.9, the best results were obtained using a Millipore
filter and porous plate column, where 85 Sr is not retained when washed with a
1 mol/L NH 4 OH solution.
Figure 3.10 shows the study performed to evaluate the behaviour of the
selected filter materials with the use of irradiated Y 2 O 3 (after dissolution in a
2 mol/L HNO 3 solution by heating).
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